Letter Sequence Supplement |
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MONTHYEARGNRO-2011/00017, Request for Additional Information Regarding Extended Power Uprate2011-03-0909 March 2011
Request for Additional Information Regarding Extended Power Uprate
Project stage: Request
ML11112A0982011-04-21021 April 2011
Request for Additional Information Regarding Extended Power Uprate
Project stage: Request
GNRO-2011/00034, Request for Additional Information Regarding Extended Power Uprate2011-05-0303 May 2011
Request for Additional Information Regarding Extended Power Uprate
Project stage: Request
GNRO-2011/00076, License Amendment Request Criticality Safety Analysis and Technical Specification 4.3.1, Criticality2011-09-0909 September 2011
License Amendment Request Criticality Safety Analysis and Technical Specification 4.3.1, Criticality
Project stage: Request
ML1127700622011-10-0303 October 2011
Acceptance Review Email, License Amendment Request, Revise Criticality Safety Analysis and Technical Specification 4.3.1, Criticality, and Delete Spent Fuel Pool Loading Criteria License Condition
Project stage: Acceptance Review
ML12271A3022012-07-25025 July 2012
E-mail Grand Gulf Station, Unit 1 - Redacted, Request for Additional Information, Amendment Request to Revise Criticality Safety Analysis and Technical Specification 4.3.1, Criticality, and Delete Spent Fuel Pool Loading Criteria License Co
Project stage: RAI
GNRO-2012/00120, Responses to NRC Requests for Additional Information – GGNS Criticality Safety Analysis License Amendment Request2012-10-0101 October 2012
Responses to NRC Requests for Additional Information – GGNS Criticality Safety Analysis License Amendment Request
Project stage: Response to RAI
ML12312A2382013-01-0202 January 2013
Request for Withholding Information from Public Disclosure, 9/28/12 Affidavit Executed by L. Trosman, GNF-A, for Attachment 1 to GNRO-2012/00120 Dated 10/1/12
Project stage: Withholding Request Acceptance
ML13071A1542013-04-0101 April 2013
Redacted Version, Request for Additional Information, Round 2, License Amendment Request, Revise Criticality Safety Analysis and TS 4.3.1, Criticality, and Delete Spent Fuel Pool Loading Criteria License Condition
Project stage: RAI
ML13091A1952013-04-0101 April 2013
Proposed Audit Plan for 4/3/13-4/4/13 Audit of the Criticality Safety Analysis; Request to Revise Criticality Safety Analysis and TS 4.3.1, Criticality, and Delete Spent Fuel Pool Loading Criteria License Condition
Project stage: Other
ML13091A1922013-04-0101 April 2013
Email, Proposed Audit Plan for 4/3/13-4/4/13 Audit of the Criticality Safety Analysis; Request to Revise Criticality Safety Analysis and TS 4.3.1, Criticality, and Delete Spent Fuel Pool Loading Criteria License Condition
Project stage: Other
ML13121A3332013-05-17017 May 2013
Audit Report for the April 3-4, 2013 Audit of the Calculations Related to the Request to Revise the Criticality Safety Analysis and TS 4.3.1, Criticality, and Delete Spent Fuel Pool Loading Criteria License Condition
Project stage: Other
GNRO-2013/00050, Criticality Safety Analysis License Amendment Request - Responses to NRC Requests for Additional Information2013-07-0202 July 2013
Criticality Safety Analysis License Amendment Request - Responses to NRC Requests for Additional Information
Project stage: Response to RAI
GNRO-2013/00063, Notification of Spent Fuel Cask Use2013-09-0505 September 2013
Notification of Spent Fuel Cask Use
Project stage: Request
GNRO-2013/00066, Criticality Safety Analysis License Amendment Request - Supplemental Information2013-09-0505 September 2013
Criticality Safety Analysis License Amendment Request - Supplemental Information
Project stage: Supplement
GNRO-2013/00073, Criticality Safety Analysis License Amendment Request - Supplemental Information2013-09-16016 September 2013
Criticality Safety Analysis License Amendment Request - Supplemental Information
Project stage: Supplement
ML13261A2642013-09-25025 September 2013
Redacted Version, Issuance of Amendment No. 195, Revise Criticality Safety Analysis and Technical Specification 4.3.1, Criticality, and Delete Spent Fuel Pool Loading Criteria License Condition
Project stage: Approval
ML13197A1922013-11-25025 November 2013
Request for Withholding Information from Public Disclosure, 6/26/13 Affidavit Executed by L. Trosman, GNF-A, for Attachment 1 to GNRO-2013/00050 Dated 7/2/2013
Project stage: Withholding Request Acceptance
2013-01-02
[Table View] |
Text
GNRO-2013/00073 September 16, 2013 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Criticality Safety Analysis License Amendment Request -
Supplemental Information Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29
REFERENCES:
- 1. Entergy Operations, Inc. letter to the NRC (GNRO-2011/00076),
License Amendment Request - Criticality Safety Analysis and Technical Specification 4.3.1, Criticality, September 9, 2011 (ADAMS Accession No. ML1125321287)
- 2. Entergy Operations, Inc. letter to the NRC (GNRO-2013/00050),
Criticality Safety Analysis License Amendment Request - Responses to NRC Requests for Additional Information, July 2, 2013 (ADAMS Accession No. ML13190A043)
Dear Sir or Madam:
In Reference 1, Entergy Operations, Inc. (Entergy) submitted to the NRC a license amendment request (LAR), which proposes to: 1) revise the criticality safety analysis (CSA) for the spent fuel and new fuel storage racks; 2) impose additional requirements for the spent fuel and new fuel storage racks in Technical Specification (TS) 4.3.1, Criticality; and 3) delete the spent fuel pool loading criteria Operating License (OL) condition.
In Reference 2, Entergy submitted to the NRC responses to Requests for Additional Information (RAIs) pertaining to Reference 1.
In a telephone call with the NRC staff on September 13, 2013, Entergy identified that the response to RAI 3.a.1, provided in Attachment 3 of Reference 2, required additional, clarifying information and that Table 3-2 provided in that response contained an error. The clarifying information and the correction are provided below.
Clarifying Information The values given in Table 3-2 of the RAI response were determined by treating the 95/95 Boraflex configuration uncertainty (see RAI 3.c.2 provided in Reference 2) as a bias.
Entergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Bryan S. Ford Senior Manager, Licensing Tel. (601) 368-5516
GNRO-2013/00073 Page 2 of 2 Correction Table 3-2 denotes the value of KLD Bias as 0.00287. Entergy discovered this value to be incorrect; the correct value is 0.00278. The last two digits of the value were inadvertently transposed when the table was developed. The remaining values in the table were checked and determined to be correct. This error has no impact on any result presented in the RAI response.
This letter contains no new commitments.
If you have any questions or require additional information, please contact Guy Davant at (601) 368-5756.
I declare under penalty of perjury that the foregoing is true and correct; executed on September 16, 2013.
Sincerely, BSF/ghd cc:
Mr. Steven A. Reynolds Regional Administrator (acting), Region IV U. S. Nuclear Regulatory Commission 1600 East Lamar Blvd.
Arlington, TX 76011-4511 State Health Officer Mississippi Department of Health P. O. Box 1700 Jackson, MS 39215-1700 U. S. Nuclear Regulatory Commission ATTN: Mr. A. B. Wang, NRR/DORL (w/2)
ATTN: ADDRESSEE ONLY ATTN: Courier Delivery Only Mail Stop OWFN/8 B1 11555 Rockville Pike Rockville, MD 20852-2378 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150
